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Journal Articles

ITER magnet systems; From qualification to full scale construction

Nakajima, Hideo; Hemmi, Tsutomu; Iguchi, Masahide; Nabara, Yoshihiro; Matsui, Kunihiro; Chida, Yutaka; Kajitani, Hideki; Takano, Katsutoshi; Isono, Takaaki; Koizumi, Norikiyo; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

The ITER organization and 6 Domestic Agencies (DA) have been implementing the construction of ITER superconducting magnet systems. Four DAs have already started full scale construction of Toroidal Field (TF) coil conductors. The qualification of the radial plate manufacture has been completed, and JA and EU are ready for full scale construction. JA has qualified full manufacturing processes of the winding pack with a 1/3 prototype and made 2 full scale mock-ups of the basic segments of TF coil structure to optimize and industrialize the manufacturing process. Preparation and qualification of the full scale construction of the TF coil winding is underway by EU. Procurement of the manufacturing equipment is near completion and qualification of manufacturing processes has already started. The constructions of other components of the ITER magnet systems are also going well towards the main goal of the first plasma in 2020.

Journal Articles

Status report on the toroidal field coils for the ITER project

Savary, F.*; Bonito Oliva, A.*; Gallix, R.*; Knaster, J.*; Koizumi, Norikiyo; Mitchell, N.*; Nakajima, Hideo; Okuno, Kiyoshi; Sborchia, C.*

IEEE Transactions on Applied Superconductivity, 20(3), p.381 - 384, 2010/06

 Times Cited Count:18 Percentile:29.02(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Installation and test programme of the ITER poloidal field conductor insert (PFCI) in the ITER test facility at JAEA Naka

Nunoya, Yoshihiko; Takahashi, Yoshikazu; Hamada, Kazuya; Isono, Takaaki; Matsui, Kunihiro; Oshikiri, Masayuki; Nabara, Yoshihiro; Hemmi, Tsutomu; Nakajima, Hideo; Kawano, Katsumi; et al.

IEEE Transactions on Applied Superconductivity, 19(3), p.1492 - 1495, 2009/06

 Times Cited Count:1 Percentile:86.75(Engineering, Electrical & Electronic)

The ITER Poloidal Field Conductor Insert (PFCI) was constructed to characterize the performance of selected cable-in-conduit NbTi conductors for the ITER Poloidal Field (PF) under relevant operating conditions. The PFCI was installed and tested inside the bore of the ITER CS model coil, which provides the background magnetic field. The PFCI is a single-layer solenoid, wound from about 50 m of a full-size ITER cable-in-conduit conductor. The winding diameter and height are about 1.5 m and 1 m, respectively. The nominal design current of the conductor is 45 kA at 6 T and 5 K. The main items in the PFCI test programme are current sharing temperature (Tcs) measurements, critical current (Ic) measurements and AC loss measurement. The key technology of the installation, the test methods and procedures, and some preliminary results of the testing campaigns are described and discussed in this paper.

Journal Articles

Conceptual design of magnet system for JT-60 super advanced (JT-60SA)

Kizu, Kaname; Tsuchiya, Katsuhiko; Ando, Toshinari*; Sborchia, C.*; Masaki, Kei; Sakurai, Shinji; Sukegawa, Atsuhiko; Tamai, Hiroshi; Fujita, Takaaki; Matsukawa, Makoto; et al.

IEEE Transactions on Applied Superconductivity, 17(2), p.1348 - 1352, 2007/06

 Times Cited Count:4 Percentile:68.39(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Predictive analysis of the ITER poloidal field conductor insert (PFCI) test program

Zanino, R.*; Astrov, M.*; Bagnasco, M.*; Baker, W.*; Bellina, F.*; Ciazynski, D.*; Egorov, S. A.*; Kim, K.*; Kvitkovic, J. L.*; Lacroix, B.*; et al.

IEEE Transactions on Applied Superconductivity, 17(2), p.1353 - 1357, 2007/06

 Times Cited Count:4 Percentile:68.39(Engineering, Electrical & Electronic)

The PFCI will be tested at JAEA Naka, inside the bore of the ITER Central Solenoid Model Coil. The main test program are the DC characterization of the conductor, the measurement of AC losses in conductor, the hydraulic characterization, the stability and the quench propagation, and the effects of cycling electromagnetic load. Based on and in support of this test program, an extensive campaign of predictive analysis has been initiated on a subset of the above-mentioned test program items and the results of the comparison of selected predictions from different laboratories will be presented and discussed. A sudden quench at 5.7-6.2 K and 45 kA is predicted. The computed temperature increase at the winding outlet is about 0.5 K for the pulse. These results will be compared with the experiment and used for an accurate prediction of the PF coil performance.

Journal Articles

Acoustic emission and disturbances in central solenoid model coil for international thermonuclear experimental reactor

Arai, K.*; Ninomiya, Akira*; Ishigooka, Takeshi*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Vieira, R.*; Martovetsky, N.*; Sborchia, C.*; Alekseev, A.*; et al.

Cryogenics, 44(1), p.15 - 27, 2004/01

 Times Cited Count:3 Percentile:83.27(Thermodynamics)

no abstracts in English

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